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Том 121, № 3 (2017)

Article

Offset-Cardinality Phase Diagram Method of Controlling Reactor Power

Aver’yanova S., Vokhmyanina N., Zlobin D., Filimonov P., Kuznetsov V., Lagovskii V.

Аннотация

The method of routine control of the power release in the VVER-1000 reactor using the offset-cardinality phase diagram is examined. This method minimizes the changes in the local power release accompanying a change in the running values of the reactor power and the axial offset, characterizing the unevenness of the power distribution over the core height. The results of computational validation of the method are presented. The rules for using offset-cardinality diagrams for operating units of VVER-1000 are presented.

Atomic Energy. 2017;121(3):155-160
pages 155-160 views

Evaluation of the Effect of Linear Scattering Anisotropy and Boundary Shape on the Calculation of K for VVER-1000 Cells with Mixed Uranium-Plutonium Power-Grade Fuel

Sultanov N.

Аннотация

The method of surface pseudo sources for solving the multigroup neutron transport equation with scattering anisotropy and different boundary conditions by the operator splitting method was developed previously. The method was implemented in the RATsIYa option of the WIMS-SH-2.0 complex. The impact of scattering anisotropy and the form of the boundary conditions on K of VVER-1000 reactor cells with uranium-plutonium power-grade fuel was investigated. The calculations showed that the impact of each of these two effects is about 0.5%; they have different signs, as a result of which they largely compensate one another.

Atomic Energy. 2017;121(3):161-165
pages 161-165 views

Development and Verification of a Model of RVK-500, -1000 Recombiners for Modeling the Containment Shells of NPP with VVER by Computational Hydrodynamics

Tarasov O., Kiselev A., Filippov A., Yudina T., Grigoruk D., Koshmanov D., Keller V., Khristenko E.

Аннотация

A model of a passive autocatalytic hydrogen recombiner (RVK-500, -1000) for use in hydrodynamic calculations of hydrogen transport and recombination processes in a VVER containment shell during a severe accident is described. The model includes calculation of the efficiency of the recombiner, the hydraulic resistance to gas flow through the recombiner, and heat losses owing to radiation from the casing of the recombiner. The model was parameterized and verified on experiments performed on a stand at VTI and INPK RET for hydrogen-air compositions with hydrogen volume fraction up to 10%. Good agreement was obtained between the calculations and experiments. Its simplicity and efficacy make it possible to use the model in hydrodynamic calculations of processes with recombiners in a real containment shell.

Atomic Energy. 2017;121(3):166-172
pages 166-172 views

Prediction of Oscillations of the Thermodynamic Parameters of the Cooling System of the IBR-2M Reactor Using Neural Nets

Pepelyshev Y., Tsogtsaikhan T.

Аннотация

The problem of predicting the oscillations of the main thermodynamic parameters of the core in the first loop of the sodium cooling system of IBR-2M reactor is examined. Attention is focused mainly on the prediction of the temperature and sodium flow at the entry into the core as well as the thermal power. It is shown that the prediction makes it possible to reduce by a factor of 3 the influence of slow oscillations of reactivity on the power and thereby reduce the operational requirements for the automatic power stabilization system. Neural-net prediction using nonlinear autoregression nets with feedback is proposed. The results agree with experiment to within ~5%.

Atomic Energy. 2017;121(3):173-178
pages 173-178 views

Use of the CFD-Code CONV-3D in Reactor Applications

Chudanov V., Aksenova A., Makarevich A., Pervichko V., Reyes I.

Аннотация

The results of testing the CONV-3D code and methods of direct numerical modeling, using supercomputers, of turbulent flows in the elements of nuclear power plants are presented for problems as close as possible to real processes: natural and forced convection of sodium in the upper plenums of the Monju nuclear power plant in Japan and mixing of the two flows at different temperatures in the secondary loop of the Phénix reactor in France. The particularities of the method for calculating the thermo- and hydrodynamic characteristics of the equipment in nuclear power plants are listed.

Atomic Energy. 2017;121(3):179-184
pages 179-184 views

Particularities of Steel Structural Elements of Reactor Facilities with Heavy Liquid Metal Coolant

Beznosov A., Bokov P., Bokova T., Makhov K.

Аннотация

The experimental investigations performed at NGTU of the characteristics of the near-wall layer in the flow of a heavy liquid metal coolant as well as the influence of the regime parameters of the loop (velocity of liquid metal coolant over contact surfaces, thermodynamic activity of oxygen, coolant temperature, and circulation time) on the change of its operating characteristics – surface roughness of the structural material during prolonged contact with high-temperature coolant flow (lead, lead–bismuth) – are analyzed.

Atomic Energy. 2017;121(3):185-191
pages 185-191 views

Hydrolysis of Sodium Beryllate in Beryllium Hydroxide Production Technology

Matyasova V., Nikolaevskii V., Alekberov Z.

Аннотация

Experimental studies of the hydrolysis of sodium beryllate, which plays an important role in the production of beryllium hydroxide, are expounded. The influence of the caustic modulus on the completeness of beryllium extraction into hydroxide and the decomposition kinetics of sodium beryllate are studied. The parameters of hydrolysis in application to alkali solutions of autoclave breakdown of beryllium-containing concentrate are presented. It is shown that aluminum can be efficiently separated from beryllium during hydrolysis of sodium beryllate.

Atomic Energy. 2017;121(3):192-196
pages 192-196 views

Application of Quasi-Ideal Cascades and the Dilution Operation for Purification of Regenerated Uranium Hexafluoride

Palkin V.

Аннотация

Purification of regenerated uranium in a two-cascade scheme with a dilution operation is proposed. The first cascade has one feed flow, two product flows, and one waste flow. It is calculated as an ideal cascade with adjustment of the obtained 235U concentration to a prescribed content in the exterior flows. Lowenrichment uranium hexafluoride, intended for the fabrication of nuclear fuel, is obtained in the primary product. A product with the same 235U concentration as in the feed flow and reduced 232,234U is produced in the intermediate product of the cascade. This product is enriched with 235U in the second cascade, which is an R-cascade with the key components 235,236UF6. The enriched uranium hexafluoride obtained in the product is diluted to 235U concentration below 5%. The 236U content decreases as a result.

Atomic Energy. 2017;121(3):197-202
pages 197-202 views

Study of the Present-Day Geodynamics of the Nizhnekansk Massif for Safe Disposal of Radioactive Wastes

Tatarinov V., Kaftan V., Seelev I.

Аннотация

The results of a study of the present-day motions of the Earth’s crust, using GPS/GLONASS satellite systems, within the Nizhnekansk massif (Krasnoyarsk krai), where the construction of an underground repository for the disposal of high-level radioactive wastes is planned. Observations conducted in 2010–2014 have provided new information about the regime of present-day motions at the junction of the largest tectonic structures region – the Siberian platform and West Siberian plate as unified parts having deep geodynamic force sources. On the whole, no anomalous values of present-day motions of the Earth’s crust, suggesting the presence of tectonic instability of the geological environment, have been recorded.

Atomic Energy. 2017;121(3):203-207
pages 203-207 views

Possibility of Obtaining High-Activity 177Lu in the IR-8 Research Reactor

Boldyrev P., Zagryadskii V., Erak D., Kurochkin A., Markovskii D., Mikhin O., Proshin M., Khmyzov N., Chuvilin D., Yashin Y.

Аннотация

The results of the production of the medical isotope 177Lu in the IR-8 research reactor are presented. The quantitative and qualitative characteristics of the desired radionuclide are determined. The radiochemical method of separating 177Lu from an irradiated target 176Yb by a combination of two electrochemical processes – cementation of ytterbium from acetate-chloride solution on sodium amalgam and electrolysis of an ytterbium solution in a single electrolytic cell – is proposed. The purification factor for removal of 176Yb from 177Lu was 105–106.

Atomic Energy. 2017;121(3):208-213
pages 208-213 views

Radioecological Validation of the Extraction Parameters of Fission Products and Actinides from Spent Nuclear Fuel from the BREST-OD-300 Reactor

Spiridonov S., Perevolotskii A., Aleksakhin R., Spirin E., Vlaskin G.

Аннотация

The aim of this work is to validate the extraction parameters of fission products and actinides from the spent nuclear reactor fuel of the BREST-OD-300 reactor on the basis of the concept of radio-ecological balance. The dose loads due to long-lived high-level wastes and natural uranium are compared for humans. Different variants of extraction of fissile materials U, Pu, and Np from spent fuel with residual content in the wastes 0.1–1% of the initial content and americium with residual content in the wastes 0.1–10% of the initial content with decay period of the spent fuel in the range 1–100 years were taken as initial data. It was found that for the indicated variants of reprocessing it is impossible to achieve radioecological balance for humans after 500 years without extracting 99Tc with residual content in the wastes not exceeding 5% of the initial content in the spent fuel. The time to achieve balance can be reduced to 300 years with additional extraction of 137Cs.

Atomic Energy. 2017;121(3):214-219
pages 214-219 views

Parrad System and Its Testing on Real Radioactive Emissions Into the Atmosphere

Arutyunyan R., Pripachkin D., Sorokovikova O., Semenov V., Ignatov R., Gubenko I., Blagodatskikh D., Rubinshtein K., Smirnova M.

Аннотация

A system for predicting accidental dissemination of radionuclides into the atmosphere at operating NPP (PARRAD) is described. The methodological and functional components of the system are presented. The results of testing the system on examples of accidental emissions at the Fukushima NPP, an incident at a heavy machine building plant in Elektrostal, and emissions in the ACURATE experiment are presented.

Atomic Energy. 2017;121(3):220-226
pages 220-226 views

Microwave Method of Identifying Explosions

Kotov Y., Semenova T., Fedorov V.

Аннотация

The informative parameters of microwave signals making it possible for distinguish by means of passive radiolocation a nuclear explosion in the atmosphere among other sources of microwave radiation (lightning or accident at NPP) and to evaluate the power and altitude of the explosion are discussed. The wavelengths falling within the atmospheric transparency range from several millimeters to tens of centimeters are examined.

Atomic Energy. 2017;121(3):227-233
pages 227-233 views

Erratum

Erratum to: Experimental-Computational Investigation of the Energy-Release Field and Field Burnup in IRT

Bushuev A., Zubarev V., Kozhin A., Haddad K., Alferov V., Portnov A., Shchurovskaya M.
Atomic Energy. 2017;121(3):234-234
pages 234-234 views